Skip to content
Radiation Materials Science Research Group Logo
  • Welcome
  • Background
  • People
  • Projects
    • Candidate Materials Evaluation for the Supercritical Water-Cooled Reactor
    • A Mechanistic Basis for Irradiation Assisted Stress Corrosion Cracking
    • Accelerator-Based Study of Irradiation Creep of Pyrolytic Carbon Used in TRISO Fuel Particles for Very High Temperature Reactors (VHTR)
    • Acquisition of a Research Grade Ion Implanter for Research and Education in Ion Beam Modification of Materials
    • Alloys for 1000°C Service in the Next Generation Nuclear Plant
    • BWRVIP Highly Irradiated Stainless Steel Crack Growth
    • Consortium on Cladding and Structural Materials for Advanced Nuclear Energy Systems
    • Constant Extension Rate Testing of Alloy 690 in Supercritical Water
    • High Temperature Materials for the Gas-Cooled Fast Reactor
    • Localized Deformation as a Primary Cause of Irradiation Assisted Stress Corrosion Cracking
    • Radiation-Induced Segregation and Phase Stability in Candidate Alloys for the Advanced Burner Reactor
    • Stress Corrosion Cracking and Corrosion of Candidate Alloys for the Supercritical Water Reactor Concept
    • Stress Corrosion Cracking of Neutron Irradiated Cast Stainless Steels in High Temperature Water
  • Publications
  • Facilities

Contact

Gary Was

Gary Was

gsw@umich.edu

(734) 763-4675

1911 Cooley

Hello world!

Posted on July 15, 2013 (June 22, 2021) by Nicole Heffernan

Welcome to CoE WordPress Sites. This is your first post. Edit or delete it, then start blogging!

Radiation Materials Science Research Group

Michigan Engineering

1221 Beal Ave. Ann Arbor, MI 48109-2102

+1 (734) 647-7000

Contact the College

© 2022 The Regents of the University of Michigan | Safety Information | Acceptable Use |Privacy Policy |U-M Main

Login | Logout